A NUCLEAR FUEL ELEMENT FOR A PRESSURIZED WATER REACTOR AND A METHOD FOR MANUFACTURING THE SAME

Abstract: The present invention relates to a nuclear fuel element for a pressurized-water reactor, PWR. The fuel element comprises cladding tubes or cladding tubes and guide tubes, whose composition and manufacture are so adapted that the cladding or the cladding and the guide tubes during reactor operation show a good resistance to general corrosion and a low hydrogen contents. This can be achieved by allowing the cladding or the cladding and the guide tubes, when being manufactured, to undergo heat treatments which are of such a nature that the cumulative annealing parameter SIGMA A = SIGMA ti exp (-Q/RTi) is at most 1.25 x 10<-14>, at Q/R = 31726 K.

Description: A nuclear fuel element for a pressurized water reactor and a method for manufacturing the same. TECHNICAL FIELD The present invention relates to a nuclear fuel element for a pressurized-water reactor, PWR. The fuel element comprises cladding tubes and guide tubes, the composition and manu¬ facture of which are so adapted that the cladding and the guide tubes during reactor operation show good resistance to general corrosion and a low hydrogen absorption. BACKGROUND ART, PROBLEMS Fuel elements for pressurized-water reactors comprise a number of fuel rods arranged in a square lattice in a frame comprising guide tubes, top tie plate, bottom tie plate and spacers. The fuel rods comprise cladding tubes inside of which the nuclear fuel is enclosed. It is of extreme impor¬ tance that thick or flaking oxide layers do not build up on the cladding tubes during reactor operation, so that the thermal conduction through the cladding is influenced or that radioactive oxide flakes spread in the reactor systems. It is also of importance that thick oxide layers do not build up on the guide tubes. The hydrogen which is generated during oxidation of zirconium should not be absorbed to any major extent by the cladding or the guide tubes since this hydrogen, which is precipitated in the form of zirconium hydride, may cause a considerable reduction of the mecha¬ nical strength of the cladding and the guide tubes. It is known to influence the composition and manufacture of the cladding tube in order thus to improve the corrosion proper¬ ties of the nuclear fuel element. In, for example, EP 196 286, a method is described for manu- facturing a cladding tube with improved corrosion properties for pressurized-water reactors. The cladding tube consists of a zirconium alloy with alloying additives of 1 to 5 % from the group Sn, Fe, Cr and Ni. To improve the corrosion properties of the tube and to achieve equilibrium in the zirconium alloy between secondary phases and matrix such that a minimum of iron is in solid solution, it is described that the tube during manufacture, after extrusion of the tube blank has been carried out, is to be heat-treated between the cold-rolling stages at a temperature in the interval 650°C to 790°C. The time for the heat-treatments is determined by the desire that the cumulative annealing parameter of the material shall exceed a certain value. The annealing parameter is calculated according to A = t exp (-Q/RT) , where t = annealing time in hours, Q = the activa¬ tion energy in cal/mole, T = the temperature in K, and T is the general gas constant. According to the patent specifica¬ tion, the annealing parameter A shall exceed 2.3 • 10 ~14 (the activation energy estimated at 6500 cal/mole) , which means that the annealing time at 700°C shall be at least 10.3 h. To obtain an additional precipitation of the secondary phase, an extra heat treatment at 540-650°C can be intro¬ duced before the last rolling stage. The literature contains a large number of publications desc¬ ribing different ways of calculating the A-parameter and different ways of determining the activation energy. Accor¬ ding to "Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding", ASTM STP 1023, the tendency to corrosion of a PWR cladding is correlated by a cumulative annealing parameter. Figures 7 and 8 show that the corrosion properties are better for claddings manufactured with a high cumulative annealing parameter. An optimum value of the cumulative annealing parameter is given as 10" 17 h, which corresponds to an annealing time of 7.1 h at 700°C (Q/R = 40 000 K) . According to "Behaviour of Structural Materials For Fuel and Control Elements in Light Water Cooled Reactors", IAEA Symposium on Improvements in Water Reactor Fuel Technology and Utilization, a cladding tube for PWR fuel is to be heat-treated at a temperature exceeding 700°C on at least one annealing occasion for obtaining good corrosion properties. According to EP 296 972, a cladding tube for pressurized- water reactors is to be manufactured of zirconium alloy and preferably of Zircaloy-4, and as a last stage in the manufacture the cladding is to undergo a so-called beta- quenching when the tube is heated to a temperature in the interval 950° to 1250°C and thereafter rapidly cooled. However, it has proved that a PWR cladding which is heat- treated in such a way that it has obtained a high A para- meter has a high hydrogen absorption fraction, i.e. of the hydrogen which is formed during the corrosion process a large percentage will be absorbed by the cladding, which leads to an embrittlement of the cladding. SUMMARY OF THE INVENTION According to the present invention, a fuel element for a PWR is obtained, the cladding of which has good corrosion resis¬ tance and low hydrogen absorption. Also the guide tubes of the fuel element can be designed, according to the present invention, so as to attain good corrosion resistance and low hydrogen absorption. The invention is defined in the claims It has proved that a PWR cladding with good corrosion resis¬ tance and low hydrogen absorption can be obtained by manu¬ facturing the cladding tube of Zircaloy-2 or a zirconium alloy based on Zircaloy-2. The composition of Zircaloy-2 is 1.2 - 1.7 per cent by weight (in the following "%") Sn, 0.07 - 0.20 % Fe, 0.05 - 0.15 % Cr, 0.03 - 0.08 % Ni, and O.09 - 0.16 % 0. Other suitable zirconium alloys are 1 - 2.0 % Sn, 0.07 - 0.70 % Fe, 0.05 - 0.15 % Cr, 0.06 - 0.40 % Ni, 0.015 - 0.20 % Nb, 0.09 - 0.16 % O, or an alloy with zirconium and 1 - 2.0 % Sn, 0.07 - 0.70 % Fe, 0.05 - 0.15 % Cr, 0.16 - 0.40 % Ni, 0.015 - 0.20 % Nb, 0.015 - 0.05 % Si, 0.09 - 0.16 % 0, and for all alloys contents of impurities normally occurring in reactor grade zirconium. When manufacturing the cladding tube, this shall be heat- treated in such a way that the cumulative annealing para¬ meter attains a low value, preferably lower than 1.25 x 10" 14 , for Q/R = 31726 K. To obtain a low value of the annealing parameter, the heat treatments between the cold-rolling stages are to be carried out at low tempera¬ tures, below 650°C and preferably below 600°C. By manufacturing cladding tubes with a special composition according to the above and with a low cumulative annealing parameter, cladding tubes for PWR fuel can be manufactured in a simpler manner and high heat-treatment temperatures and low heat treatments need not be utilized. A fuel element whose cladding combines good corrosion resis¬ tance and low hydrogen absorption can be used for higher burnups with a reduced risk of oxide scaling forming on the cladding and of high hydrogen contents entailing unfavour¬ able embrittlement of the cladding. It has also proved possible to improve the guide tubes by making them from an alloy with the composition according to what has been stated above for cladding tubes and that the guide tubes during manufacture are heat-treated in such a way as has been described above for cladding tubes. A fuel element according to the invention may comprise guide tubes and fuel rods, the claddings of which are manufactured according to the method described above, or the fuel element may comprise fuel rods whose claddings are manufactured according to the method described above whereas the guide tubes are manufactured in a different way. Example 1 A nuclear fuel element for a PWR comprises a lattice of 17 x 17 fuel rods. The fuel rods comprise fuel pellets enclosed in a sealed cladding tube. The cladding is manufactured in such a way that the cumulative annealing parameter is lower than 1.25 x 10 -14 , for Q/R = 31726 K. During manufacture of cladding tubes for fuel elements according to the invention, conventionally the starting material is a forging of a zir- coniu alloy comprising 1.2 - 1.7% Sn, 0.18 - 0.24% Fe, 0.07 - 0.13% Cr, 0.16 - 0.40% Ni, 0.015 - 0.20% Nb, 0.002 -0.05% Si, 0.09 - 0.20% 0, the balance being zirconium with impurities normally occurring in reactor grade zirconium. The forging is treated, beta-quenched and extruded in con¬ ventional manner. After extrusion, the tube is machined in four cold-rolling operations into the desired final dimen¬ sion. Between all cold-rolling operations, the tube under¬ goes intermediate annealing at 500°C for 1, hour and after the last cold rolling a final annealing is performed at 460°C for 1.5 hours. The manufacture described gives a cumulative annealing-parameter of 5 x 10 ~18 . Example 2 A nuclear fuel element for a PWR comprises fuel rods whose cladding is manufactured from Zircaloy-2. The cladding is manufactured by cold-rolling the tube, after extrusion, in six stages until the final dimension is attained and with intermediate annealings at 625°C for 6 hours. After the last cold rolling, the cladding tube is finally heat-treated at 540°C for 4 hours. The cumulative annealing parameter of the cladding tube is 1.25 x 10 -14 .

Claims: CLAIMS 1. A nuclear fuel element for a pressurized-water reactor, PWR, comprising a frame comprising guide tubes, top tie and bottom tie plates and spacers, as well as fuel rods arranged in the frame comprising fuel pellets sealed in a fuel cladding, characterized in that the cladding consists of Zircaloy-2 or a zirconium alloy with 1 - 2.0% Sn, 0.07 - 0.70% Fe, 0.05 - 0.15% Cr, 0.06 - 0.40% Ni, 0.015 - 0.20% Nb, 0.09 - 0.16% 0, or an alloy with 1 - 2.0% Sn, 0.07 - 0.70% Fe, 0.05 - 0.15% Cr, 0.16 - 0.40% Ni, 0.015 - 0.20% Nb, 0.015 - 0.05% Si, 0.09 - 0.16% 0, and for all alloys zirconium with contents of impurities normally occurring in reactor grade zirconium, and that the cladding is manufac- tured in such a way that its cumulative annealing parameter ∑A = ∑ti exp (-Q/RTi) is at most 1.25 x 10 -14 , at Q/R = 31726 K. 2. A nuclear fuel element according to claim 1, characterized in that the guide tubes consist of Zircaloy- 2 or a zirconium alloy with 1 - 2.0% Sn, 0.07 - 0.70% Fe, 0.05 - 0.15% Cr, 0.06 - 0.40% Ni, 0.015 - 0.20% Nb, 0.09 - 0.16% 0, or an alloy with 1 - 2.0% Sn, 0.07 - 0.70% Fe, 0.05 - 0.15% Cr, 0.16 - 0.40% Ni, 0.015 - 0.20% Nb, 0.015 - 0.05% Si, 0.09 - 0.16% 0, and for all alloys zirconium with con¬ tents of impurities normally occurring in reactor grade zirconium, and that the guide tubes are manufactured in such a way that their cumulative annealing parameter ∑A = ∑ti exp (-Q/RTi) is at most 1.25 x 10" 14 , at Q/R = 31726 K. 3. A nuclear fuel element according to claim 1 or 2, characterized in that when manufacturing the cladding, after the extrusion of a tube blank, the cladding is heat- treated between cold-rolling operations at temperatures below 650°C and preferably below 600°C. 4. A nuclear fuel element according to claim 1, 2 or 3, characterized in that the cladding is finally heat-treated at 400 to 600°C. 5. A nuclear fuel element according to claim 1, 2, 3 or 4, characterized in that when manufacturing the guide tubes, after the extrusion of a tube blank, the guide tubes are heat-treated between the cold-rolling operations at temperatures below 650°C and preferably below 600°C. 6. A method for manufacturing cladding tubes and guide tubes or only cladding tubes for nuclear fuel elements intended for a pressurized-water reactor, PWR, comprising extrusion of a tube blank, cold rollings, with intermediate heat treatments, until the final dimension is attained, and a final heat treatment after the last cold rolling, characterized in that the cumulative annealing parameter ∑A = ∑ti exp (-Q/RTi) is at most 1.25 x 10" 14 , at Q/R = 31726 K. 7. A method according to claim 6, characterized in that the cladding tube and the guide tube or only the cladding tube is/are manufactured from Zircaloy-2 or from a zirconium alloy with 1 - 2.0% Sn, 0.07 - 0.70% Fe, 0.05 - 0.15% Cr, 0.06 - 0.40% Ni, 0.015 - 0.20% Nb, 0.09 - 0.16% O, or an alloy with 1 - 2.0% Sn, 0.07 - 0.70% Fe, 0.05 - 0.15% Cr, 0.16 - 0.40% Ni, 0.015 - 0.20% Nb, 0.015 - 0.05% Si, 0.09 - 0.16% O, and for all alloys zirconium with contents of impurities normally occurring in reactor grade zirconium. 8. A method according to claim 6 or 7, characterized in that the cladding tube and the guide tube or only the cladding tube when being manufactured, after the extrusion of a tube blank, is/are heat-treated between cold rolling operations at temperatures below 650°C and preferably below 600°C. 9. A method according to claim 6, 7 or 8, characterized in that the cladding and the guide tube or only the cladding tube is/are finally heat-treated at 400 to 600°C.

Inventors: RUDLING PETER, RUDLING, PETER
Applicants: ASEA ATOM AB, RUDLING PETER, ABB ATOM AB, RUDLING, PETER
Application year: 1994
Main classification: G21C3
IPC codes: C22F1, G21C3